ML20028C845
| ML20028C845 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/23/1982 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028C841 | List: |
| References | |
| TASK-***, TASK-TM 50-313-82-29, 50-368-82-27, NUDOCS 8301140216 | |
| Download: ML20028C845 (4) | |
See also: IR 05000313/1982029
Text
c
4
. .
,
.
, :l ,
-
..
.
TABLE 1
_
LICENSEE COMMITMENTS REVIEWED
.
LOREG-0737 " Clarification of TMI Action Plan Requirements"
NUREG-0737 Item
Subject
I.A.1.1
Shift Technical Advisor - Training
I.A.1.3
Shift Manning
I.C.1
Inadequate Core Cooling Procedures.
'I.C.5
Feedback of Operating Experience
I.C.6
Verify correct Performance'of Operating
Activities
II.B.1
RCS Vents
,
II.B.2
Plant Shielding
II.B.3
Post-Accident Sampling
II.B.4
Training of Mitigating Core Damage
II.D.1
Relief and Safety Valve Testing
II.E.1.1
AFW System Evaluation
II.E.1.2
AFW Auto Start and Flow indication
II.E.4.2.5
Containment Pressure Setpoint
II.E.4.2.6
Containment Isolation - Purge Valves
II.E.4.2.7
Containment Isolation -. Radiation
Signal
II.F.1.1
Noble Gas Monitor
II.F.1.2
' Iodine /Particular Sampling
'
!
!
0301140216 821223
PDR ADOCK 05000313
G ,
- ...
._. _
__
. -
.
- . _ . .
. _ _
- - - , .
.
_ , ,
_.
.
. _
_
_
.-
_
_
_ _ . - -
,
,
t
'
.
,
2
.
NUREG-073'7 Item
Subject
-
II.F.1.3
Containment _Hi-range monitor
l.
'
II.F.1.4
Containee,nt Pressure
II.F.1.5.
Containment Waste Level
II.F.1.6
Containment Hydrogen
.
II.F.2
Instrumentat' ion for' Detection of
_
Inadequate Core _ Cooling
II.K.2.13
= Thermal-Mechanical Report
II.K.2.17
. Voiding in the Reactor Coolant System
II.K.2.19
' Sequential Auxiliary Feedwater Flow
II.K.3.3
-Report on Safety / Relief Valve Failures
and challenges
.
II.K.3.5
Automatic Trip of RCP During a LOCA
II.K.3.17
ECC System Outages
II.K.3.25
Power on Pump Seals
II.K.3.30
Small Break LOCA Methods
III.A.1.2
Upgrade Emergency Support Facilities
,
III.D.3.3
Inplant Radiation Monitoring
III.D.3.4
Within these 33 line items, a total of 84 commitments or statements were verified.
NRR Generic Letters
Letter Date or Number
Subject
September 21, 1979
Followup of Multiple Equipment Failures
and Surveillance Testing Errors
October 17, 1979
Lessons Learned from Release at North
Anna
November 9, 1979
Fuel Clad Swelling
_
February 23, 1980
Containment Isolation Valves
,
,e-
,- , ,, ,
, , , - -
,- ,-
w
,.- , - -
--
s x
-
.
-
- -
.-
,
3-
r
Letter Date or Number
Subject
June 11, 1980
Decay Heat Technical Specifications
July 31, 1980
-Staffing Requirements
December 15, 1980
FSAR Update
,
81-04
Station Blackout-
81-14
Seismic Qu'alification of Auxiliary Feed
'
81-19
Thermal Shock to Reactor Pressure Vessel
,
81-21
Natural Circulation Cooldown
t
81-28
Steam Generator Overfill
Within these 12 generic letters, a total of 22 commitments or-statments were
verified.
IE Bulletins
,
Bulletin
Subject
j
79-06B
TMI Issues
!
79-09
GE Circuit Breakers
79-13
Cracking in Feedwater System Piping
79-11
Westinghouse Relays
79-18
Audioility of Evacuation Alarms
79-19
Radioactive Waste Management
79-23
Diesel Generator Field Exciter
Transformer
'
79-24
Frozen Lines
79-25
Westinghouse Relays
'
79-28
Namco Switches
-80-05
Vacuum Conditon in Tanks
>-
80-10
Contamination of Nonradioactive System
80-11
Masonry Wall Design
.
.
_. .,
-~
- ._,
_
-
. . ..
_._
_ .
-
.
-
_
-
-
b
-
r
_
1
.
>
4
,
4
!
Bulletin'
Subject
.
-
80-12
-
Decay Heat _ Removal Operability;
-
~
80-15
~Possible Loss of Emergency
Notification System
,
80-16
Rosemount Pressure Transmitters
80-18
Minimum Flow Through Centrifugal
Charging Pumps-
~
80-24
Flooding of. Containment Sump
80-20
Westinghouse Switches
y
81-01-
Mechanical Snubbers
-
81-02
Failure of Gate Values to Close
'
-Against Differential
Of the 21 IEB's contained in this review, a total of 29 specific commitments
or statements.
'
^
l
NRC Inspection Reports'
Item
50-313/80-03, 50-368/80-03
'
50-313/80-05
<
,
50-313/80-06, 50-368/80-06
50-313/80-10, 50-368/80-10
50-313/80-15, 50-368/80-15
.
~
l
-
1
2
l
. - -.
-
-
..-
..- .
-.-
-
._. . - . - , . -
,-